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Volume 1

Number 1 | Number 2 | Number 3 | Number 4 | Number 5 | Number 6

Number 1

Liquid Metal Breeder Reactor (LIMB) Nuclear Evaluation

Robert J. Teitel, John B. Brown

Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 13-24

Technical Paper / dx.doi.org/10.13182/NT65-A20459

Experience with High Pressure Heavy-Water Systems at NPD

A. C. Hoyle, G. R. Howey

Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 25-32

Technical Paper / dx.doi.org/10.13182/NT65-A20460

Excursion-Limiting Fuse for the Mixed Spectrum Critical Assembly

K. Hikido, G. V. Brynsvold, H. F. Johnston

Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 33-38

Technical Paper / dx.doi.org/10.13182/NT65-A20461

Effects of 1.0% Superimposed Mean Strain on the Bending Fatigue Strength of Zircaloy-4

D. F. Mowbray

Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 39-48

Technical Paper / dx.doi.org/10.13182/NT65-A20462

Analysis of a Radioisotope Thrustor-Auxiliary Power Unit

David F. Berganni, Robert R. Barthelemy

Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 49-54

Technical Paper / dx.doi.org/10.13182/NT65-A20463

Fast Reactor Fuel Burnup

F. R. Channon, J. D. Luoma, E. D. Frankhouser

Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 55-61

Technical Paper / dx.doi.org/10.13182/NT65-A20464

Void-Fraction Measurements in Cavitating Mercury

Frederick G. Hammitt, Willy Smith, Ian E. B. Lauchlan, Richard D. Ivany, M. John Robinson

Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 62-68

Technical Paper / dx.doi.org/10.13182/NT65-A20465

Out-of-Pile Steam-Fraction Determination by Neutron-Beam Attenuation

William T. Sha, Charles F. Bonilla

Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 69-75

Technical Paper / dx.doi.org/10.13182/NT65-A20466

The Education, Experience, Training, and Certification of Reactor Operators at AEC-Owned Reactors

Walter S. Wilgus, Whittie J. McCool

Nuclear Technology / Volume 1 / Number 1 / February 1965 / Pages 76-81

Technical Paper / dx.doi.org/10.13182/NT65-A20467

Number 2

The Settled-Bed Fast-Reactor Concept—1 000-MWe Reactor Design

L. Green, M. M. Levine, A. Aronson, W. Bent, D. A. Goellner, J. J. McNicholas, G. Nugent, G. Pancer, H. Susskind, J. Chernick, D. Gurinsky, L. P. Hatch

Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 107-130

Technical Paper / dx.doi.org/10.13182/NT65-A20478

Fuel Management for an Intermediate Power Research Reactor

Ernest E. Hill

Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 131-135

Technical Paper / dx.doi.org/10.13182/NT65-A20479

Production of the Heaviest Elements by Multiple Neutron Capture

J. Milsted, P. R. Fields, D. N. Metta

Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 136-144

Technical Paper / dx.doi.org/10.13182/NT65-A20480

The Radioisotope-Powered Bimetallic-Disk Engine

Calvin C. Silverstein

Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 145-150

Technical Paper / dx.doi.org/10.13182/NT65-A20481

Reactor Production of 109 Cd: Isotopic Composition and Use as an X-Ray Source

Howard T. Russell

Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 151-154

Technical Paper / dx.doi.org/10.13182/NT65-A20482

Electrodeposition of 99Tc Metal

Technetium metal can be electrodeposited almost quantitatively from dilute solutions of pertechnetate ion in acidic ammonium oxalate. Films up to 18 mg/cm2 have been deposited as dense adherent coatings on copper, gold, silver and platinum at a current density of 1.3 amp/cm2.

Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 155-157

Technical Paper / dx.doi.org/10.13182/NT65-A20483

Vacuum Distillation of Magnesium Metal

W. D. Box

Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 158-159

Technical Paper / dx.doi.org/10.13182/NT65-A20484

Effect of Elevated-Temperature Irradiation on Hastelloy N

W. R. Martin, J. R. Weir

Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 160-167

Technical Paper / dx.doi.org/10.13182/NT65-A20485

Behavior of Uranium Sulfide Fast-Reactor-Type Fuel Specimens Under Transient Heating in Treat

L. E. Robinson, C. E. Dickerman, R. Carlander, C. August, C. Mueller

Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 168-175

Technical Paper / dx.doi.org/10.13182/NT65-A20486

Radiation Exposures in Fabricating 233U-Th Fuels

J. P. Nichols, R. E. Brooksbank, D. E. Ferguson

Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 176-178

Technical Paper / dx.doi.org/10.13182/NT65-A20487

Determination of Zirconium by Activation and Chemical Separation of 97Nb

T. K. Choy, H. R. Lukens, G. H. Andersen

Nuclear Technology / Volume 1 / Number 2 / April 1965 / Pages 179-183

Technical Paper / dx.doi.org/10.13182/NT65-A20488

Number 3

N S Savannah Containment Integrity, Its Measurement and Improvement

James H. Taylor

Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 213-218

Technical Paper / dx.doi.org/10.13182/NT65-A20504

Head-end Dissolution for UC Processes and UC-PuC Reactor Fuels

J. R. Flanary, J. H. Goode, M. J. Bradley, L. M. Ferris, J. W. Ullmann, G. C. Wall

Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 219-224

Technical Paper / dx.doi.org/10.13182/NT65-A20505

The Evaluation and Measurement of Reactor-Safety Performance

H. J. Larson, K. Stratton

Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 225-229

Technical Paper / dx.doi.org/10.13182/NT65-A20506

Fabrication of Radioactive Samples for Cross-Section Measurements

J. R. Berreth

Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 230-234

Technical Paper / dx.doi.org/10.13182/NT65-A20507

General Corrosion of Incoloy-800® in Simulated Superheat Reactor Environment

W. L. Pearl, E. G. Brush, G. G. Gaul, G. P. Wozadlo

Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 235-245

Technical Paper / dx.doi.org/10.13182/NT65-A20508

Corrosion-Rate-Law Considerations in Superheated Steam

E. G. Brush

Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 246-251

Technical Paper / dx.doi.org/10.13182/NT65-A20509

The Failure of Stressed Zircaloy in Aqueous Chloride Solutions

K. C. Thomas, R. J. Allio

Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 252-258

Technical Paper / dx.doi.org/10.13182/NT65-A20510

Technique for Optimizing the Composition of Regenerating-Neutron-Flux Monitors

W. L. Bunch

Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 259-266

Technical Paper / dx.doi.org/10.13182/NT65-A20511

Continuous On-reactor Measurement of Instantaneous Corrosion Rates

R. B. Richman

Nuclear Technology / Volume 1 / Number 3 / June 1965 / Pages 267-270

Technical Paper / dx.doi.org/10.13182/NT65-A20512

Number 4

Engineering Development of a Fluid-bed Fluoride Volatility Process I Bench-Scale Studies

D. Ramaswami, N. M. Levitz, A. A. Jonke

Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 293-300

Technical Paper / dx.doi.org/10.13182/NT65-A20525

Engineering Development of a Fluid-bed Fluoride Volatility Process II Pilot-Scale Studies

John T. Holmes, Howard Stethers, John J. Barghusen

Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 301-309

Technical Paper / dx.doi.org/10.13182/NT65-A20526

Hydrogen Reduction of Pu(IV) to Pu(III)

Robert H. Rainey

Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 310-311

Technical Paper / dx.doi.org/10.13182/NT65-A20527

Neutron and Gamma-Ray Die-Away in a Heterogenous System

W. R. Mills, Jr., L. S. Allen, F. Selig, R. L. Caldwell

Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 312-321

Technical Paper / dx.doi.org/10.13182/NT65-A20528

Design and Economic Study of a Gas-phase Chemonuclear Ozone Process

M. Beller, D. Goellner, M. Steinberg

Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 322-326

Technical Paper / dx.doi.org/10.13182/NT65-A20529

244Cm Production and Separation—Status of the Pilot Production Program at Savannah River

Harold J. Groh, Richard T. Huntoon, Carl S. Schlea, James A. Smith, Fred H. Springer

Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 327-336

Technical Paper / dx.doi.org/10.13182/NT65-A20530

Displacement Spike Effects in Copper-rich Copper-Iron Alloys

A. Boltax

Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 337-347

Technical Paper / dx.doi.org/10.13182/NT65-A20531

Preparation of PuC Pellets by Vacuum Sintering

O. L. Kruger

Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 348-355

Technical Paper / dx.doi.org/10.13182/NT65-A20532

A Three-Decade Exponential Current Generator for Testing Reactor Period Meters

James H. Talboy

Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 356-358

Technical Paper / dx.doi.org/10.13182/NT65-A20533

A Comparison of Shielding Calculations with Absolute Measurements in Massive Shields

Erkki J. Aalto

Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 359-374

Technical Paper / dx.doi.org/10.13182/NT65-A20534

Microdetermination of Ruthenium in Uranium Compounds

O. A. Vita, C. F. Trivisonno

Nuclear Technology / Volume 1 / Number 4 / August 1965 / Pages 375-380

Technical Paper / dx.doi.org/10.13182/NT65-A20535

Number 5

Ordered Packed-Bed Fuel Elements

H. Susskind, W. E. Winsche, W. Becker

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 405-411

Technical Paper / dx.doi.org/10.13182/NT65-A20549

Stainless-Steel-Clad Fuel Rod Failures

R. N. Duncan, W. H. Arlt, H. E. Williamson, C. J. Baroch, J. P. Hoffmann, T. J. Pashos

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 413-418

Technical Paper / dx.doi.org/10.13182/NT65-A20551

Evaluation of Highly Irradiated Yankee Fuel Cladding

W. R. Smalley

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 419-424

Technical Paper / dx.doi.org/10.13182/NT65-A20552

Performance of Thin-Walled Stainless-Steel-Clad Fuel Rods

D. R. McClintock, E. Paxson, H. M. Ferrari

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 425-431

Technical Paper / dx.doi.org/10.13182/NT65-A20553

Boron Stainless-Steel Fuel-Element Cladding in the Indian Point Reactor

C. R. Johnson

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 432-438

Technical Paper / dx.doi.org/10.13182/NT65-A20554

Fatigue and Burst Tests on Irradiated In-Pile Stainless-Steel Pressure Tubes

L. A. Waldman, M. Doumas

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 439-445

Technical Paper / dx.doi.org/10.13182/NT65-A20555

Corrosion Product Behavior in Stainless-Steel-Clad Water Reactor Systems

G. Russell Taylor, Paul Cohen

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 446-452

Technical Paper / dx.doi.org/10.13182/NT65-A20556

Development of Test to Simulate Intergranular Cracking of Nonsensitized Stainless Steel in Water Reactor Environments

A. E. Pickett, W. L. Pearl, M. C. Rowland

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 453-461

Technical Paper / dx.doi.org/10.13182/NT65-A20557

Radiation Effects on the Mechanical Properties and Microstructure of Type-304 Stainless Steel

J. S. Armijo, J. R. Low, U. E. Wolff

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 462-477

Technical Paper / dx.doi.org/10.13182/NT65-A20558

Influence of Preirradiation Heat Treatment on the Postirradiation Ductility of Stainless Steel

W. R. Martin, J. R. Weir

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 478-483

Technical Paper / dx.doi.org/10.13182/NT65-A20559

Inhibition of Chloride Stress Corrosion Cracking of Austenitic Stainless Steel

C. R. Bergen

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 484-489

Technical Paper / dx.doi.org/10.13182/NT65-A20560

Formation of Cyanide in Liquid Sodium

E. W. Hobart, R. G. Bjork

Nuclear Technology / Volume 1 / Number 5 / October 1965 / Pages 490-492

Technical Paper / Technical Note / dx.doi.org/10.13182/NT65-A20561

Number 6

Liquid-Metal Boiling Heat Transfer

Y. S. Tang

Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 521-537

Technical Paper / dx.doi.org/10.13182/NT65-A20579

Effective Resonance Temperature Correlation of UO2

William T. Sha

Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 538-545

Technical Paper / dx.doi.org/10.13182/NT65-A20580

A Nuclearly Safe Triangular-Slab Tank for Handling Enriched Uranium

C. E. Newlon, R. J. Clouse, A. J. Mallett

Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 546-547

Technical Paper / dx.doi.org/10.13182/NT65-A20581

Gamma-Ray-Induced Chlorination of Benzene

Richard E. Faw, John M. McCabe, Herbert S. Isbin

Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 548-555

Technical Paper / dx.doi.org/10.13182/NT65-A20582

Production of Carrier-Free 132Cs and 129Cs

Virginia H. Wilson, W. N. Bishop, Manny Hillman

Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 556-559

Technical Paper / dx.doi.org/10.13182/NT65-A20583

Pyrolytic-Carbon Coatings on Ceramic Fuel Particles

R. L. Beatty, F. A. Carlsen, Jr., J. L. Cook

Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 560-566

Technical Paper / dx.doi.org/10.13182/NT65-A20584

Fluidized-Bed Process for Production of Tungsten

J. H. Oxley, E. A. Beidler, J. M. Blocher, Jr., C. J. Lyons, R. S. Park, J. H. Pearson

Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 567-574

Technical Paper / dx.doi.org/10.13182/NT65-A20585

Vapor Deposition and Characterization of Tungsten-Rhenium Alloys

J. I. Federer, C. F. Leitten, Jr.

Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 575-580

Technical Paper / dx.doi.org/10.13182/NT65-A20586

Suppression of Grain Growth in Vapor-Deposited Tungsten up to 2500°C

A. F. Weinberg, J. R. Lindgren, N. B. Elsner, R. G. Mills

Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 581-583

Technical Paper / dx.doi.org/10.13182/NT65-A20587

Thermochemical Reduction of Uranium Hexafluoride for the Direct Fabrication of Uranium Dioxide Ceramic Fuels

R. L. Heestand, C. F. Leitten, Jr.

Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 584-588

Technical Paper / dx.doi.org/10.13182/NT65-A20588

Fabrication of 20wt%Ti-V Alloy Tubing for Nuclear Fuel Cladding

W. R. Burt, Jr., W. C. Kramer, F. J. Karasek, R. M. Mayfield

Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 589-596

Technical Paper / dx.doi.org/10.13182/NT65-A20589

Absolute Liquid-Scintillation Rate Constants and Fluorescence Efficiencies

H. R. Lukens, Jr.

Nuclear Technology / Volume 1 / Number 6 / December 1965 / Pages 597-602

Technical Paper / dx.doi.org/10.13182/NT65-A20590